Preliminary Study on Utilization of Carbon Dioxide as a Coolant of High Temperature Engineering Test Reactor with MOX and Minor Actinides Fuel
- Bosscha Laboratory, Department of Physics, Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, INDONESIA Jl. Ganesa 10 Bandung 40132 (Indonesia)
High temperature engineering test reactor (HTTR) is an uranium oxide (UO2) fuel, graphite moderator and helium gas-cooled reactor with 30 MW in thermal output and outlet coolant temperature of 950 deg. C. Instead of using helium gas, we have utilized carbon dioxide as a coolant in the present study. Beside that, uranium and plutonium oxide (mixed oxide, MOX) and minor actinides have been employed as a new fuel type of HTTR. Utilization of plutonium and minor actinide is one of the support system to non-proliferation issue in the nuclear development. The enrichment for uranium oxide has been varied of 6-20% with plutonium and minor actinides concentration of 10%. In this study, burnup period is 1100 days. The reactor cell calculation was performed by using SRAC 2002 code, with nuclear data library was derived from JENDL3.2. Reactor core calculation was done by using CITATION module. The result shows that HTTR can achieve its criticality condition with 14% of {sup 235}U enrichment.
- OSTI ID:
- 21410478
- Journal Information:
- AIP Conference Proceedings, Vol. 1244, Issue 1; Conference: ICANSE 2009: 2. international conference on advances in nuclear science and engineering 2009, Bandung (Indonesia), 3-4 Nov 2009; Other Information: DOI: 10.1063/1.3462747; (c) 2010 American Institute of Physics; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CARBON DIOXIDE
COMPUTERIZED SIMULATION
COOLANTS
CRITICALITY
ENRICHMENT
FISSION
GRAPHITE
HELIUM
HTTR REACTOR
ISOTOPE SEPARATION
NUCLEAR DATA COLLECTIONS
NUCLEAR FUELS
PLUTONIUM OXIDES
PROLIFERATION
REACTOR CELLS
REACTOR CORES
REACTOR FUELING
URANIUM 235
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CARBON
CARBON COMPOUNDS
CARBON OXIDES
CHALCOGENIDES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EVEN-ODD NUCLEI
EXPERIMENTAL REACTORS
FLUIDS
FUELS
GAS COOLED REACTORS
GASES
GRAPHITE MODERATED REACTORS
HEAVY NUCLEI
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATERIALS
MINERALS
MINUTES LIVING RADIOISOTOPES
NONMETALS
NUCLEAR REACTIONS
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
RADIOISOTOPES
RARE GASES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SEPARATION PROCESSES
SIMULATION
SPONTANEOUS FISSION RADIOISOTOPES
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM ISOTOPES
URANIUM OXIDES
YEARS LIVING RADIOISOTOPES